imronuke / KOMODOLinks
Open Nuclear Reactor Simulator
☆59Updated 2 months ago
Alternatives and similar repositories for KOMODO
Users that are interested in KOMODO are comparing it to the libraries listed below
Sorting:
- An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool☆24Updated 4 years ago
- THOR is a radiation transport code for unstructured meshes.☆14Updated 9 months ago
- Stochastic Calculator Of Neutron transport Equation☆44Updated 2 weeks ago
- Collection of scripts for managing data for OpenMC☆33Updated 5 months ago
- Native plotting GUI for model design and verification☆59Updated 5 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆111Updated 4 months ago
- Monte Carlo Particle Lists☆32Updated 2 weeks ago
- detailed cad model of the msre☆37Updated 4 months ago
- Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.☆28Updated last month
- Sampling nuclear data and uncertainty☆51Updated last week
- High-Fidelity Multiphysics☆112Updated this week
- Framework for REsearch in Nuclear ScIence and Engineering☆15Updated 3 years ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆69Updated last month
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆41Updated last year
- MC/DC: Monte Carlo Dynamic Code☆41Updated 2 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated last year
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆154Updated this week
- CGMF nuclear fission fragment de-excitation statistical code☆25Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆59Updated 2 months ago
- Example Jupyter notebooks for OpenMC☆36Updated 4 months ago
- Collection of models for reactor physics benchmarks☆53Updated 8 months ago
- The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) Software☆18Updated 11 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆24Updated 9 months ago
- ☆80Updated last year
- Nuclear data processing with legacy NJOY☆110Updated last month
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆36Updated last week
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆47Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆42Updated last month
- Tools to translate between different CSG geometry types☆39Updated last month
- Convert MCNP input files to a general CAD format☆37Updated last week